Flammable gas safety program. Analytical methods development: FY 1993 progress report

Campbell, J. Argyll; Clauss, S.A.; Grant, K. E.; Hoopes, V.; Lerner, B.; Lucke, R.B.; Mong, Gary M.; Rau, John A.; Steele, R.

doi:10.2172/10122073

Cited by 18 publications

(25 citation statements)

References 8 publications

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“…tanks SY-101 and SY-103 were shipped from Hanford to LANL for Tc removal experiments with ReillexT"-HPQ. These wastes contain relatively high concentrations of organic complexants (Campbell et al, 1993). Ion exchange column experiments on CC simulants and batch contact experiments on the actual CC waste samples were performed at LANL to determine the equilibrium and kinetic parameters for Tc removal using the ReillexTM-HPQ material.…”

Section: Needmentioning

confidence: 99%

Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

Blanchard¹,

Kurath²,

Golcar

et al. 1996

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@ This document was printed on recycled paper. (9197)t r SummaryThis report describes two bench-scale column tests conducted to demonstrate the removal of Tc-99 from actual alkaline high salt radioactive waste. The waste used as feed for these tests was obtained fromlhe Hanford double shell tank AW-101 , which contains double shell slurry feed (DSSF). The tank sample was diluted to approximately 5 M Na with water, and most of the Cs-137 was removed using crystalline silicotitanates. The tests were conducted with two small columns connected in series, containing 10 mL of either a sorbent, ABEC 5000 (Eichrom Industries, Inc.), or an anion exchanger Reillex?-HPQ (Reilly Industries, Inc.). Both materials are selective for pertechnetate anion (TcO4-). The process steps generally followed those expected in a full-scale process and included 1) resin conditioning, 2) loading, 3) caustic wash to remove residual feed and prevent the precipitation of Al(OH)3, and 4) elution. A small amount of Tc-99m tracer was added as ammonium pertechnetate to the feed and a portable GEA counter was used to closely monitor the process. Analyses of the Tc-99 in the waste was performed using ICP-MS .with spot checks using radiochemical analysis. Technetium x-ray absorption spectroscopy ( U S ) spectra of 6 samples were also collected to determine the prevalence of non-pertechnetate species [e.g. Tc(IV)].Some of the relevant flow test parameters are given in Table S The 1525% of the Tc-99 that was not extracted corresponds to a Tc-99 level in the effluent of 1.65 X 10-2 Cum3 to 2.75 X 10-2 Ci/m3. This is 5.5% to 9.2% of the NRC Class A limit of 0.3 Ci/m3. The concentration in the final waste form would likely be higher.The relatively high fraction of non-pertechnetate Tc-99 in the AW-101 waste suggests that this phenomenon may be common in the tank wastes. It was expected that significant fractions of non-pertechnetate Tc-99 would be restricted to tank wastes with a high organic content. The DSSF from AW-101 contains a relatively low amount of organic ( approx. 2.5 g TOC/L in tank).As indicated by the So values, the effective Tc-99 capacity of the Reillexm-HPQ is greater than that for the ABEC 5000 material. The difference between the h50 values for the Tc-99m tracer data and the actual Tc-99 data is attributed to the non-pertechnetate fraction in the waste.Both materials are efficiently eluted, but the ABEC 5000 material is eluted with deionized water which would contribute a relatively small amount of other components to a final waste form.Few operational problems were experienced with either material, although a small portion of the ReillexT"-HPQ bed on the second column was observed to float in solution and preparation of the ABEC 5000 column was tedious because of the difficulty in removing entrained air from the bed. It is suggested that a larger particle size would alleviate this problem.--

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Section: Needmentioning

confidence: 99%

Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

Blanchard¹,

Kurath²,

Golcar

et al. 1996

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“…In To address this need we adapted existing methods for cesium ion removal currently performed on flammable gas tank waste (Campbell et al 1994) to the ferrocyanide tank waste. This method has been successfully demonstrated for the removal of significant levels of radioactivity from tank samples to allow bench-top handling.…”

Section: Influence Ofph On Nitrite Reactivity With Fe(cn)z-mentioning

confidence: 99%

Ferrocyanide Safety Program cyanide speciation studies. Final report

Bryan¹,

Pool²,

Bryan³

1995

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“…The positive ion spectrum of NTA is shown in Figure 3. 22. The (M+Na)+ ion is at m/z 215 and the di-Na ion at m/z 237.…”

Section: Under Rapid Heating Conditions Organic Compounds Favor Vapomentioning

confidence: 99%

“…The identity of the most concentrated component was verified with high resolution MS measurements. B.19 The chelators and chelator fragments constitute only 20-50% of the TOC; it has been shown that the remaining components are low-molecular-weight acids such as oxalic, glycolic, and formic acid (22). Certain of these chelator components in the radioactive environment of the waste tanks degrade rapidly.…”

Section: Deuterated Edta As a Surrogate Tracermentioning

confidence: 99%

Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report; Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report

Clauss¹,

Grant²,

Hoopes³

et al. 1996

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Flammable gas safety program. Analytical methods development: FY 1993 progress report

Cited by 18 publications

References 8 publications

Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

Ferrocyanide Safety Program cyanide speciation studies. Final report

Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report; Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report

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